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Richard F. Wright
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Journal Articles

A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors

Jun Liao, Katsuhiro Ohkawa, William L. Brown, Richard F. Wright
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041701.
Paper No: NERS-18-1088
https://doi.org/10.1115/1.4042796
Published Online: July 19, 2019
View Article titled, A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors
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Topics: Flow (Dynamics), Pipes, Pressure, Pressurized water reactors, Stratified flow, Water, Steam
Proceedings Papers

CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB

Hong Xu, Yiban Xu, Liping Cao, Yixing Sung, Vefa N. Kucukboyaci, Richard F. Wright
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A048, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67345
https://doi.org/10.1115/ICONE25-67345
View Paper titled, CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB
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Topics: Computational fluid dynamics, Pressurized water reactors, Flow (Dynamics), Simulation, Nuclear reactor coolants, Reactor vessels, Coolants, Design, Fuels, Modeling
Proceedings Papers

Effects of Aging on the Thermal Conductivity of the AP1000® Containment Vessel Inorganic Zinc Coating

Thomas A. Kindred, Richard F. Wright
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A028, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31157
https://doi.org/10.1115/ICONE22-31157
View Paper titled, Effects of Aging on the Thermal Conductivity of the AP1000® Containment Vessel Inorganic Zinc Coating
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Topics: Containment vessels, Thermal conductivity, Zinc coatings, Containment, Shells, Coating processes, Coatings, Corrosion, Cooling, Design
Proceedings Papers

AP1000 ® Passive Core Cooling System Performance Following an Extended Station Blackout Event

Richard F. Wright, Stephen Swantner, Matthew M. Swartz, John Lojek, Yong Jae Song, T. A. Kindred
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A050, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31129
https://doi.org/10.1115/ICONE22-31129
View Paper titled, AP1000 ® Passive Core Cooling System Performance Following an Extended Station Blackout Event
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Topics: Cooling systems, Containment, Heat, Condensed matter, Water, Steam, Temperature, Boiling, Condensation, Containment vessels
Proceedings Papers

AP1000 Passive Residual Heat Removal Heat Exchanger Confirmatory Analysis

Richard F. Wright, James R. Schwall, Creed Taylor, Naeem U. Karim, Jivan G. Thakkar, Terry Schulz
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 567-573, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89524
https://doi.org/10.1115/ICONE14-89524
View Paper titled, AP1000 Passive Residual Heat Removal Heat Exchanger Confirmatory Analysis
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Topics: Heat, Heat exchangers, Design, Safety, Geometry, Computational fluid dynamics, Computers, Containment, Containment vessels, Cooling systems
Proceedings Papers

Emergency Operating Procedures (EOPs) for the AP1000 Simulator

Yuichi Hayashi, Gianfranco Saiu, Richard F. Wright
Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 263-272, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89508
https://doi.org/10.1115/ICONE14-89508
View Paper titled, Emergency Operating Procedures (EOPs) for the AP1000 Simulator
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Topics: Emergencies, Pressurized water reactors, Safety, Accidents, Design, Nuclear reactor coolants, Boilers, Cooling, Emergency response, Leakage